BAŠIĆ, Ivica ;CRNJAC, Peter . The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krko NPP in the Case of the SB LOCA. Strojniški vestnik - Journal of Mechanical Engineering, [S.l.], v. 52, n.6, p. 404-418, august 2017. ISSN 0039-2480. Available at: <https://www.sv-jme.eu/article/the-estimated-influence-of-the-input-parameters-in-the-analysis-of-the-pts-in-the-core-of-the-pwr-kr%c2%9ako-npp-in-the-case-of-the-sb-loca/>. Date accessed: 04 oct. 2024. doi:http://dx.doi.org/.
Bašić, I., & Crnjac, P. (2006). The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krko NPP in the Case of the SB LOCA. Strojniški vestnik - Journal of Mechanical Engineering, 52(6), 404-418. doi:http://dx.doi.org/
@article{., author = {Ivica Bašić and Peter Crnjac}, title = {The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krko NPP in the Case of the SB LOCA}, journal = {Strojniški vestnik - Journal of Mechanical Engineering}, volume = {52}, number = {6}, year = {2006}, keywords = {nuclear reactors; pressure vessels; pressurized thermal chock; SB LOCA accident; }, abstract = {This paper focuses on the deterministic method of limiting cases of the Krko Nuclear Power Plant (NPP) reactor pressure-vessel cooling by mediating the emergency core-cooling system (ECCS) during a small-break loss-of-coolant accident (SB LOCA). The SB LOCA accident with the equivalent diameter break of 50.8 mm in the cold leg and the RELAP5/MOD3.3 computer code were selected for the basic calculation. In further study, by modifying the ECCSs parameters for the same break, three accidents of the SB LOCA were simulated. The purpose of our study was to estimate the potential risk of the extreme conservative input parameters for the pressurized thermal shock (PTS) in the reactors pressure vessel.}, issn = {0039-2480}, pages = {404-418}, doi = {}, url = {https://www.sv-jme.eu/article/the-estimated-influence-of-the-input-parameters-in-the-analysis-of-the-pts-in-the-core-of-the-pwr-kr%c2%9ako-npp-in-the-case-of-the-sb-loca/} }
Bašić, I.,Crnjac, P. 2006 August 52. The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krko NPP in the Case of the SB LOCA. Strojniški vestnik - Journal of Mechanical Engineering. [Online] 52:6
%A Bašić, Ivica %A Crnjac, Peter %D 2006 %T The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krko NPP in the Case of the SB LOCA %B 2006 %9 nuclear reactors; pressure vessels; pressurized thermal chock; SB LOCA accident; %! The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krko NPP in the Case of the SB LOCA %K nuclear reactors; pressure vessels; pressurized thermal chock; SB LOCA accident; %X This paper focuses on the deterministic method of limiting cases of the Krko Nuclear Power Plant (NPP) reactor pressure-vessel cooling by mediating the emergency core-cooling system (ECCS) during a small-break loss-of-coolant accident (SB LOCA). The SB LOCA accident with the equivalent diameter break of 50.8 mm in the cold leg and the RELAP5/MOD3.3 computer code were selected for the basic calculation. In further study, by modifying the ECCSs parameters for the same break, three accidents of the SB LOCA were simulated. The purpose of our study was to estimate the potential risk of the extreme conservative input parameters for the pressurized thermal shock (PTS) in the reactors pressure vessel. %U https://www.sv-jme.eu/article/the-estimated-influence-of-the-input-parameters-in-the-analysis-of-the-pts-in-the-core-of-the-pwr-kr%c2%9ako-npp-in-the-case-of-the-sb-loca/ %0 Journal Article %R %& 404 %P 15 %J Strojniški vestnik - Journal of Mechanical Engineering %V 52 %N 6 %@ 0039-2480 %8 2017-08-18 %7 2017-08-18
Bašić, Ivica, & Peter Crnjac. "The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krko NPP in the Case of the SB LOCA." Strojniški vestnik - Journal of Mechanical Engineering [Online], 52.6 (2006): 404-418. Web. 04 Oct. 2024
TY - JOUR AU - Bašić, Ivica AU - Crnjac, Peter PY - 2006 TI - The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krko NPP in the Case of the SB LOCA JF - Strojniški vestnik - Journal of Mechanical Engineering DO - KW - nuclear reactors; pressure vessels; pressurized thermal chock; SB LOCA accident; N2 - This paper focuses on the deterministic method of limiting cases of the Krko Nuclear Power Plant (NPP) reactor pressure-vessel cooling by mediating the emergency core-cooling system (ECCS) during a small-break loss-of-coolant accident (SB LOCA). The SB LOCA accident with the equivalent diameter break of 50.8 mm in the cold leg and the RELAP5/MOD3.3 computer code were selected for the basic calculation. In further study, by modifying the ECCSs parameters for the same break, three accidents of the SB LOCA were simulated. The purpose of our study was to estimate the potential risk of the extreme conservative input parameters for the pressurized thermal shock (PTS) in the reactors pressure vessel. UR - https://www.sv-jme.eu/article/the-estimated-influence-of-the-input-parameters-in-the-analysis-of-the-pts-in-the-core-of-the-pwr-kr%c2%9ako-npp-in-the-case-of-the-sb-loca/
@article{{}{.}, author = {Bašić, I., Crnjac, P.}, title = {The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krko NPP in the Case of the SB LOCA}, journal = {Strojniški vestnik - Journal of Mechanical Engineering}, volume = {52}, number = {6}, year = {2006}, doi = {}, url = {https://www.sv-jme.eu/article/the-estimated-influence-of-the-input-parameters-in-the-analysis-of-the-pts-in-the-core-of-the-pwr-kr%c2%9ako-npp-in-the-case-of-the-sb-loca/} }
TY - JOUR AU - Bašić, Ivica AU - Crnjac, Peter PY - 2017/08/18 TI - The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krko NPP in the Case of the SB LOCA JF - Strojniški vestnik - Journal of Mechanical Engineering; Vol 52, No 6 (2006): Strojniški vestnik - Journal of Mechanical Engineering DO - KW - nuclear reactors, pressure vessels, pressurized thermal chock, SB LOCA accident, N2 - This paper focuses on the deterministic method of limiting cases of the Krko Nuclear Power Plant (NPP) reactor pressure-vessel cooling by mediating the emergency core-cooling system (ECCS) during a small-break loss-of-coolant accident (SB LOCA). The SB LOCA accident with the equivalent diameter break of 50.8 mm in the cold leg and the RELAP5/MOD3.3 computer code were selected for the basic calculation. In further study, by modifying the ECCSs parameters for the same break, three accidents of the SB LOCA were simulated. The purpose of our study was to estimate the potential risk of the extreme conservative input parameters for the pressurized thermal shock (PTS) in the reactors pressure vessel. UR - https://www.sv-jme.eu/article/the-estimated-influence-of-the-input-parameters-in-the-analysis-of-the-pts-in-the-core-of-the-pwr-kr%c2%9ako-npp-in-the-case-of-the-sb-loca/
Bašić, Ivica, AND Crnjac, Peter. "The Estimated Influence of the Input Parameters in the analysis of the PTS in the Core of the PWR Krko NPP in the Case of the SB LOCA" Strojniški vestnik - Journal of Mechanical Engineering [Online], Volume 52 Number 6 (18 August 2017)
Strojniški vestnik - Journal of Mechanical Engineering 52(2006)6, 404-418
© The Authors, CC-BY 4.0 Int. Change in copyright policy from 2022, Jan 1st.
This paper focuses on the deterministic method of limiting cases of the Krko Nuclear Power Plant (NPP) reactor pressure-vessel cooling by mediating the emergency core-cooling system (ECCS) during a small-break loss-of-coolant accident (SB LOCA). The SB LOCA accident with the equivalent diameter break of 50.8 mm in the cold leg and the RELAP5/MOD3.3 computer code were selected for the basic calculation. In further study, by modifying the ECCSs parameters for the same break, three accidents of the SB LOCA were simulated. The purpose of our study was to estimate the potential risk of the extreme conservative input parameters for the pressurized thermal shock (PTS) in the reactors pressure vessel.